05000267/LER-1981-027, Forwards LER 81-027/03L-0.Detailed Event Analysis Encl

Forwards LER 81-027/03L-0.Detailed Event Analysis Encl

ML19352B149
Person / Time
Site:	Fort Saint Vrain
Issue date:	05/13/1981
From:	Warembourg D PUBLIC SERVICE CO. OF COLORADO
To:	Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19352B150	List: 05000267/LER-1981-027, Forwards LER 81-027/03L-0.Detailed Event Analysis Encl 05000267/LER-1981-027-03, /03L-0:during 810413-25,plant Operated in Degraded Mode of Limiting Conditions of Operation 4.2.10 on Five Occasions.Caused by Circulator Trips Increasing Temp Resulting in Core Offgassing
References
P-81143, NUDOCS 8106030221
Download: ML19352B149 (6)

LER-1981-027, Forwards LER 81-027/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
2671981027R00 - NRC Website

text

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Mr. Karl V. Seyf rit, Director C

Nuclear Regulatory Commission Region IV Of fice of Inspection and Enforcement 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76012 Reference: Facility Operaciag License No. DP R-34 Docket No. 50-267

Dear Mr. Seyf rit:

Enclosed please find,a copy of Reportable Occurrence Report No. 50-267/

81-027, Final,, submitted per the requirements of Technical Specification AC 7.5.2(b)2.

Also, please find enclosed one copy of the Licensee Event Report for Reportable Occurrence Report No. 50-267/81-027.

Very truly yours,

d $s L?s Don Warembourg Manager, Nuclear Production DW/cls Enclosure g

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Director, MIPC

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Td106030 W S

REPORT DATE:

May 13, 1981 REPORTABLE OCCURRENCE 81-027 ISSUE O OCCURRENCE DATE:

Aoril 13, 1981 Page 1 of 5 FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 191/2 PLATTEVILLE, Col.0RADO 80651 REPORT NO. 50-267/81-027/03-L-0 Final IDENTIFICATION OF OCCURRENCE:

Between April 12, 1981, and April 25, 1981, the plant was operated in a degraded mode of LCO 4.2.10 on five separate occasions.

These events are reportable per Fort St.

Vrain Technical Specification AC 7.5.2(b)2.

EVENT

DESCRIPTION

Event #1.

See Figure 1.

On April 12, 1981, at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />, a plant power increase to approximately 60% power was initiated.

By midnight, the core average outlet temperature was greater than 1200 degrees fahrenheit.

The total primary coolant oxidants, the sum of moisture, carbon monoxide, and carbon dioxide, had exceeded 10 parts per million (ppm). Total oxidants had peaked and started to decrease by noon of April 13. At 1435 hours0.0166 days <br />0.399 hours <br />0.00237 weeks <br />5.460175e-4 months <br />, an electrical problem occurred on reactor plant motor control cabinet #1, which resulted in a reactor scram at 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br />.

Event #2.

On April 15, 1981, during the plant recovery from the scram of April 13, average core outlet temperature was increased te greater than 1200 degrees fahienheit.

As power increased, the primary coolant oxidants also increased until at 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br />, the 10 ppm limit was exceeded.

The power level was gradually increased over the next several days to approximately 80%.

During this time, the total primary coolant oxidants cecreased.

On April 19, at 0135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br />, a hot reheat scram occurred.

Events #3 and #4.

On April 22, 1981, at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />, and again on April 23, at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />, during the plant recovery f*om the scram of April 19, primary coolant total oxidants temporarily exceeded 10 ppm.

Event

1. 5.

On April 23, while power was being increased to approximately 30%, the total primary coolant oxidants again exceeded 10 opm.

The oxidants increased until a hot reheat scram occurred at 0143 hours0.00166 days <br />0.0397 hours <br />2.364418e-4 weeks <br />5.44115e-5 months <br /> on April 25.

T.hroughout this ceriod, the helium purificator system was in operation removing contaminants from the helium.

i 1

REPORTABLE OCCURRENCE 81-027 ISSUE 0 Page 2 of 5

CAUSE

DEscRIprION:

Event #1.

The increase in primary coolant oxidants is being attributed to off gassing from the core due to increasing core temperatures during the plant startup.

Event #2.

The increase in prima ry coolant oxidants is being attributed to the moisture ingress, which resulted from the Loop 2 trip and hot reheat scram of April 13.

Events #3, #4, and #5. The increase in primary coolant oxidants is being attributed to the moisture ingress, which resulted from the circulator trip and reactor scram of April 19 and the Loop 2 trip of April 20.

CORRECTIVE A.C. TIOM -

Events #1, #2, and #5 were terminated by reactor scrams and turbine trips.

Events #3 and #4 were individual readings greater than 10 pom and no,

corrective action was taken.

There was no affect on public health or safety.

1

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REPORTABLE OCCURRENCE 81-028 ISSUE O l

Page 5 of 5 Prepared By:

IM Asa T. Keec

. Technical Services Technician i

Reviewed By:

/TechnicalServicesSupervisor

. W. 4anm Reviewed By:

Frank M. Mathie Operations Manager Approved By:

• h Don Warembourg Manager, Nuclear Production 4

,,.7,